Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor - Validation of CFD codes

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F07%3A%230000961" target="_blank" >RIV/46356088:_____/07:#0000961 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor - Validation of CFD codes

Popis výsledku v původním jazyce

The EU project FLOMIX-R was aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity.This report focuses on the computational fluid dynamics (CFD) code validation. CFD calculations have been accomplished for selected experiments with two different CFD codes (CFX, FLUENT). The matrix of benchmark cases contains slug mixing tests simulating the start-up of the first main circulation pump which have been performed with three 1:5 scaled facilities: the Rossendorf coolant mixing model ROCOM, the Vattenfall test facility and a metal mock-up of a VVER-1000 type reactor. The results of the CFDcalculations are mostly in-between the uncertainty bands of the experiments. It can be concluded about the suitability of applying CFD methods in engineering applications for turbulent mixing in nuclear reactors.

Název v anglickém jazyce

Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor - Validation of CFD codes

Popis výsledku anglicky

The EU project FLOMIX-R was aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity.This report focuses on the computational fluid dynamics (CFD) code validation. CFD calculations have been accomplished for selected experiments with two different CFD codes (CFX, FLUENT). The matrix of benchmark cases contains slug mixing tests simulating the start-up of the first main circulation pump which have been performed with three 1:5 scaled facilities: the Rossendorf coolant mixing model ROCOM, the Vattenfall test facility and a metal mock-up of a VVER-1000 type reactor. The results of the CFDcalculations are mostly in-between the uncertainty bands of the experiments. It can be concluded about the suitability of applying CFD methods in engineering applications for turbulent mixing in nuclear reactors.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JB - Senzory, čidla, měření a regulace

OECD FORD obor

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Projekt

<a href="/cs/project/FT-TA3%2F071" target="_blank" >FT-TA3/071: Bezpečnostní aspekty pokročilých jaderných reaktorů.</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2007

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

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Svazek periodika

2007

Číslo periodika v rámci svazku

237

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

17

Strana od-do

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Kód UT WoS článku

000249157000008

EID výsledku v databázi Scopus

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